CN113494704A - Nuclear power waste heat discharging device - Google Patents
Nuclear power waste heat discharging device Download PDFInfo
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- CN113494704A CN113494704A CN202010191183.5A CN202010191183A CN113494704A CN 113494704 A CN113494704 A CN 113494704A CN 202010191183 A CN202010191183 A CN 202010191183A CN 113494704 A CN113494704 A CN 113494704A
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- pipeline
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- waste heat
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- 239000002918 waste heat Substances 0.000 title claims abstract description 27
- 238000007599 discharging Methods 0.000 title description 7
- 239000007789 gas Substances 0.000 claims abstract description 98
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 56
- 239000013535 sea water Substances 0.000 claims abstract description 35
- 239000007788 liquid Substances 0.000 claims abstract description 12
- 239000000498 cooling water Substances 0.000 claims description 13
- 238000000034 method Methods 0.000 claims description 10
- 230000005494 condensation Effects 0.000 abstract description 21
- 238000009833 condensation Methods 0.000 abstract description 21
- 230000008569 process Effects 0.000 description 9
- 239000000806 elastomer Substances 0.000 description 6
- 229920001971 elastomer Polymers 0.000 description 6
- 239000000693 micelle Substances 0.000 description 5
- 239000000203 mixture Substances 0.000 description 5
- 230000009471 action Effects 0.000 description 3
- 230000001629 suppression Effects 0.000 description 3
- 230000009286 beneficial effect Effects 0.000 description 2
- 230000008859 change Effects 0.000 description 2
- 230000002349 favourable effect Effects 0.000 description 2
- 239000012530 fluid Substances 0.000 description 2
- 230000001939 inductive effect Effects 0.000 description 2
- 238000002347 injection Methods 0.000 description 2
- 239000007924 injection Substances 0.000 description 2
- 239000000243 solution Substances 0.000 description 2
- 230000004075 alteration Effects 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 238000003889 chemical engineering Methods 0.000 description 1
- 230000008878 coupling Effects 0.000 description 1
- 238000010168 coupling process Methods 0.000 description 1
- 238000005859 coupling reaction Methods 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000012535 impurity Substances 0.000 description 1
- 230000010355 oscillation Effects 0.000 description 1
- 230000000737 periodic effect Effects 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- 229920006395 saturated elastomer Polymers 0.000 description 1
- 230000000087 stabilizing effect Effects 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
Images
Classifications
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B1/00—Methods of steam generation characterised by form of heating method
- F22B1/02—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
- F22B1/16—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being hot liquid or hot vapour, e.g. waste liquid, waste vapour
- F22B1/162—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being hot liquid or hot vapour, e.g. waste liquid, waste vapour in combination with a nuclear installation
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F16—ENGINEERING ELEMENTS AND UNITS; GENERAL MEASURES FOR PRODUCING AND MAINTAINING EFFECTIVE FUNCTIONING OF MACHINES OR INSTALLATIONS; THERMAL INSULATION IN GENERAL
- F16L—PIPES; JOINTS OR FITTINGS FOR PIPES; SUPPORTS FOR PIPES, CABLES OR PROTECTIVE TUBING; MEANS FOR THERMAL INSULATION IN GENERAL
- F16L55/00—Devices or appurtenances for use in, or in connection with, pipes or pipe systems
- F16L55/04—Devices damping pulsations or vibrations in fluids
- F16L55/045—Devices damping pulsations or vibrations in fluids specially adapted to prevent or minimise the effects of water hammer
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F16—ENGINEERING ELEMENTS AND UNITS; GENERAL MEASURES FOR PRODUCING AND MAINTAINING EFFECTIVE FUNCTIONING OF MACHINES OR INSTALLATIONS; THERMAL INSULATION IN GENERAL
- F16L—PIPES; JOINTS OR FITTINGS FOR PIPES; SUPPORTS FOR PIPES, CABLES OR PROTECTIVE TUBING; MEANS FOR THERMAL INSULATION IN GENERAL
- F16L55/00—Devices or appurtenances for use in, or in connection with, pipes or pipe systems
- F16L55/04—Devices damping pulsations or vibrations in fluids
- F16L55/045—Devices damping pulsations or vibrations in fluids specially adapted to prevent or minimise the effects of water hammer
- F16L55/055—Valves therefor
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B37/00—Component parts or details of steam boilers
- F22B37/002—Component parts or details of steam boilers specially adapted for nuclear steam generators, e.g. maintenance, repairing or inspecting equipment not otherwise provided for
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- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- Mechanical Engineering (AREA)
- Physics & Mathematics (AREA)
- High Energy & Nuclear Physics (AREA)
- Thermal Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- Sustainable Development (AREA)
- Sustainable Energy (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention discloses a nuclear power waste heat discharge device which comprises a steam generation system, wherein the steam generation system comprises a liquid inlet and a steam outlet, and the steam outlet is connected with a steam discharge pipeline; a gas pipeline for introducing non-condensable gas into the steam discharge pipeline is arranged on the steam discharge pipeline, and a one-way valve for introducing the non-condensable gas into the steam discharge pipeline from the gas pipeline is arranged on the gas pipeline; the device adopts the one-way valve, when the pressure of the gas pipeline is higher than that of the steam discharge pipeline, air enters the steam discharge pipeline and has good compressibility, and the water hammer pressure can be greatly reduced; when the gas line pressure is less than the vapor discharge line pressure, the check valve closes, preventing seawater from entering the air side. The invention can automatically eliminate the phenomenon of water hammer caused by steam condensation through the opening and closing of the check valve, and improve the safety and reliability of the equipment.
Description
Technical Field
The invention belongs to the technical field of nuclear power engineering, and particularly relates to a nuclear power waste heat discharging device.
Background
When saturated Steam, wet Steam or superheated Steam directly contacts with supercooled water, Condensation phase change of the Steam is generated, and the Condensation phase change process is called Steam Direct Contact Condensation-SDCC. The heat and mass transfer resistance at the vapor-liquid two-phase condensation interface in the direct contact condensation process is extremely small, and the heat and mass transfer efficiency at the condensation interface is extremely high, so that the heat and mass transfer device is widely applied to the fields of chemical engineering, energy, nuclear power and the like. For example: a waste heat recovery system, a steam ejector, a nuclear reactor pressure suppression safety system and the like in a nuclear power station.
Chinese patent application No. CN201810833698.1 discloses a condensate water hammer suppression system in a steam discharge process, which includes: steam discharge system, air injection system and flow control system, steam outlet are with horizontal union coupling, and pressure sensor monitors different position pressure fluctuations and obtains the condensation water hammer and take place the position to control the start and stop that electrical control valve selected different air injection main roads, contain the air in the steam and can increase the thermal resistance between vapour and liquid, reduce the heat transfer coefficient that condenses. However, in this patent, the water hammer in the pipeline cannot be automatically eliminated, and the backflow of water in the pipeline cannot be prevented, so that the device capable of automatically eliminating the water hammer caused by the condensation of steam on the seawater side discharged by the nuclear power waste heat can be found, which is of great significance for the safe operation of the nuclear power device.
Therefore, how to design a device which can automatically eliminate the water hammer caused by the condensation of the steam on the seawater side discharged by the nuclear power waste heat, ensure the waste heat discharge efficiency of the system, improve the safety of the operation of the nuclear power device and other beneficial effects becomes a problem to be solved urgently.
In view of the above, the present invention is particularly proposed.
Disclosure of Invention
The invention aims to overcome the defects of the prior art and provide the nuclear power waste heat discharging device with a simple structure.
In order to solve the technical problems, the invention adopts the technical scheme that:
the nuclear power waste heat discharge device comprises a steam generation system, wherein the steam generation system comprises a liquid inlet and a steam outlet, and the steam outlet is connected with a steam discharge pipeline;
the steam exhaust pipeline is provided with a gas pipeline for introducing non-condensable gas into the steam exhaust pipeline, and the gas pipeline is provided with a one-way valve for introducing the non-condensable gas into the steam exhaust pipeline from the gas pipeline.
Further, in the above-mentioned case,
the steam generation system also comprises a high-temperature water inlet and a cooling water outlet, and a first channel is formed between the high-temperature water inlet and the cooling water outlet; and a second channel is formed between the liquid inlet and the steam outlet, and the first channel and the second channel are isolated from each other and have heat exchange.
Further, in the above-mentioned case,
the liquid inlet is communicated with a seawater pipeline, the high-temperature water inlet is communicated with a high-temperature water outlet in the nuclear power device, and the cooling water outlet is communicated with a cooling water inlet in the nuclear power device.
Further, in the above-mentioned case,
the steam discharge pipeline comprises a vertical section and an inclined section, the vertical section is connected with the steam outlet, the inclined section is an inclined pipeline with a large length-diameter ratio, an included angle between the central axis of the inclined pipeline with the large length-diameter ratio and a horizontal line is not more than 5 degrees, and the length-diameter ratio of the inclined pipeline with the large length-diameter ratio is more than 40 degrees.
Further, in the above-mentioned case,
a connecting elbow is arranged between the vertical section and the inclined section, a plurality of gas pipelines are arranged on the steam discharge pipeline, and the distance between the gas pipeline close to the connecting elbow and the connecting elbow is not more than 10 times of the major-diameter ratio of the inclined pipeline.
Further, in the above-mentioned case,
the distance between two adjacent gas pipelines is not more than 10 times of the ratio of the large length to the large diameter of the inclined pipeline.
Further, in the above-mentioned case,
one end of the gas pipeline is connected with the steam discharge pipeline, the other end of the gas pipeline is provided with a gas storage tank, and the gas storage tank is provided with a gas compressor.
Further, in the above-mentioned case,
the one-way valve is disposed adjacent to a junction of the gas conduit and the vapor vent conduit.
Further, in the above-mentioned case,
the diameter of the gas pipeline is not more than 1/5 of the large length-diameter ratio of the inclined pipeline, and the ratio of the length to the diameter of the gas pipeline is more than 20.
Further, in the above-mentioned case,
the non-condensable gasses comprise air.
After the technical scheme is adopted, compared with the prior art, the invention has the following beneficial effects.
The invention adopts the check valve, when the pressure of the gas pipeline is higher than that of the inclined pipeline with large length-diameter ratio, the air enters the inclined pipeline with large length-diameter ratio and is mixed with the steam in the pipeline, when the steam condenses to induce water hammer, the air has good compressibility as non-condensable gas, the water hammer pressure can be greatly reduced, and the air is discharged into the seawater under the driving of natural convection of the seawater; when the pressure of the gas pipeline is smaller than the pressure of the inclined pipeline with the large length-diameter ratio, the check valve is closed, seawater is prevented from flowing backwards into the cabin body, and the operation safety of the nuclear power device is ensured; once the steam condensation inducing pressure is reduced, the air automatically enters the inclined pipeline with large length-diameter ratio, the air is used as non-condensable gas for eliminating water hammer induced by steam condensation, and the process is circulated. The invention can automatically eliminate the phenomenon of water hammer caused by steam condensation through the opening and closing of the check valve, thereby eliminating noise and vibration caused by water hammer caused by steam on the seawater side in the process of discharging the nuclear power waste heat and improving the safety and reliability of equipment.
The following describes embodiments of the present invention in further detail with reference to the accompanying drawings.
Drawings
The accompanying drawings, which are included to provide a further understanding of the invention, are incorporated in and constitute a part of this specification, illustrate embodiments of the invention and together with the description serve to explain the invention without limiting the invention to the right. It is obvious that the drawings in the following description are only some embodiments, and that for a person skilled in the art, other drawings can be derived from them without inventive effort. In the drawings:
FIG. 1 is a schematic view of a nuclear power waste heat removal device of the present invention;
FIG. 2 is a schematic diagram of the principle of the present invention for suppressing water hammer from non-condensable gases;
FIG. 3 is another schematic illustration of the non-condensable gas suppression water hammer of the present invention;
in the figure: 1. a seawater pipeline; 2. a cooling water outlet; 3. a high temperature water inlet; 4. a steam outlet; 5. a vertical section; 6. an inclined pipe with a large length-diameter ratio; 7. a gas conduit; 8. a steam discharge conduit; 9. a one-way valve; 10. a gas storage tank; 11. a gas compressor; 12. the cabin side; 13. the seawater side; 14. a steam chamber; 15. elastomer micelles.
It should be noted that the drawings and the description are not intended to limit the scope of the inventive concept in any way, but to illustrate it by a person skilled in the art with reference to specific embodiments.
Detailed Description
In order to make the objects, technical solutions and advantages of the embodiments of the present invention clearer, the technical solutions in the embodiments will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and the following embodiments are used for illustrating the present invention and are not intended to limit the scope of the present invention.
In the description of the present invention, it should be noted that the terms "upper", "lower", "front", "rear", "left", "right", "vertical", "inner", "outer", etc., indicate orientations or positional relationships based on the orientations or positional relationships shown in the drawings, and are only for convenience of description and simplicity of description, but do not indicate or imply that the device or element being referred to must have a particular orientation, be constructed and operated in a particular orientation, and thus, should not be construed as limiting the present invention.
In the description of the present invention, it should be noted that, unless otherwise explicitly specified or limited, the terms "mounted," "connected," and "connected" are to be construed broadly, e.g., as meaning either a fixed connection, a removable connection, or an integral connection; can be mechanically or electrically connected; may be directly connected or indirectly connected through an intermediate. The specific meanings of the above terms in the present invention can be understood in specific cases to those skilled in the art.
As shown in fig. 1 to 3, the present invention provides a nuclear power waste heat removal device, which includes a steam generation system, wherein the steam generation system includes a liquid inlet and a steam outlet 4, and the steam outlet 4 is connected to a steam discharge pipe 8; the steam exhaust pipeline 8 is provided with a gas pipeline 7 for introducing non-condensable gas into the steam exhaust pipeline 8, and the gas pipeline 7 is provided with a one-way valve 9 for introducing the non-condensable gas into the steam exhaust pipeline 8 from the gas pipeline 7.
Further, the steam generating system also comprises a high-temperature water inlet 3 and a cooling water outlet 2, and a first channel is formed between the high-temperature water inlet 3 and the cooling water outlet 2; a second channel is formed between the liquid inlet and the vapor outlet 4, and the first channel and the second channel are isolated from each other and have heat exchange. The liquid inlet is communicated with a seawater pipeline 1, the high-temperature water inlet 3 is communicated with a high-temperature water outlet in the nuclear power device, and the cooling water outlet 2 is communicated with a cooling water inlet in the nuclear power device.
Specifically, in a waste heat discharge system of the nuclear power device, a steam generation system is usually a heat exchanger, a hot end fluid for heat exchange in the heat exchanger is high-temperature water discharged from the nuclear power device, a cold end fluid is seawater, the seawater absorbs heat from the high-temperature water, the heat is transferred to the seawater and discharged into the sea, the waste heat in the nuclear power device is discharged by utilizing the infinite and wide characteristics of the sea, and the danger caused by overhigh internal energy of the nuclear power device is avoided; in detail, after the seawater is heated to boiling by high-temperature and high-pressure water in the heat exchanger, the steam-water mixture enters the steam discharge pipeline 8 through the steam outlet 4, when the mass flow rate of the steam-water mixture is low, the steam and the seawater meet in the steam discharge pipeline 8, the direct contact condensation phenomenon can occur, and even the condensation can occur to induce water hammer. The steam in the steam discharge pipeline 8 meets the seawater, the steam is wrapped by the supercooled water due to the condensation effect of the steam to form a closed steam cavity 14, the steam is continuously condensed and suddenly condensed, a low-pressure area is generated in the condensation area, the surrounding seawater flows in an accelerated manner under the action of pressure difference, and the accelerated seawater enables the residual steam to be compressed and rapidly collapsed under the action of inertia force. When the steam bubbles collapse, the seawater has a higher speed and collides with each other to form a water hammer. A water hammer occurs in the steam discharge pipe 8 and the pressure exhibits a periodic sharp fluctuation. Strong vibrations and noise are induced in the pipeline, and severe fluctuations in pressure and temperature pose a serious threat to the integrity, safety and concealment of the nuclear power plant.
According to the invention, the steam discharge pipeline 8 is provided with the gas pipeline 7 for introducing the non-condensable gas into the steam discharge pipeline 8, the gas pipeline 7 is provided with the one-way valve 9 for introducing the non-condensable gas into the steam discharge pipeline 8 from the gas pipeline 7, the non-condensable gas is introduced into the steam discharge pipeline 8, an elastic body is formed by utilizing the good compressibility of the non-condensable gas, the accelerated seawater collides on the elastic body and then the elastic body contracts under the action of collision, so that the energy generated by collision is well absorbed and buffered, a water hammer is not formed in the steam discharge pipeline 8, at the moment, the pressure in the steam discharge pipeline 8 rises in a small range, the pressure in the gas pipeline 7 is smaller than the pressure in the steam discharge pipeline 8, and the one-way valve 9 is closed. When the steam continues to be condensed to induce the pressure in the steam discharge pipe 8 to decrease, air automatically enters the steam discharge pipe 8 through the one-way valve 9 to eliminate the water hammer induced by the condensation of the steam, and the process is circulated. As shown in fig. 2 and 3, the amplitude of the pressure oscillation in the pipe is reduced due to the presence of the non-condensable gasses in the steam discharge pipe 8. The invention can automatically eliminate the phenomenon of water hammer caused by steam condensation through the opening and closing of the one-way valve 9, thereby eliminating noise and vibration caused by water hammer induced by steam on the seawater side 13 in the process of discharging the nuclear power waste heat and improving the safety and reliability of equipment on the cabin side 12.
Further, steam escape pipe 8 includes vertical section 5 and slope section, the slope section is 6 pipes of a big length to diameter ratio slope, the central axis that 6 pipes of big length to diameter ratio slope and the contained angle between the water flat line do not exceed 5, the length to diameter ratio that 6 pipes of big length to diameter ratio slope is greater than 40.
Specifically, the steam discharge pipeline 8 comprises a vertical section 5 and an inclined section, the vertical section 5 is connected with the steam outlet 4, the steam-water mixture firstly passes through the vertical section 5 at a distance and then enters the inclined section, the steam-water proportion in the steam-water mixture is increased to the maximum extent, and the generation of water hammer is favorably prevented, further, as shown in fig. 2, the inclined section is designed into an inclined pipe 6 with a large length-diameter ratio, so that when the mass flow of the steam-water mixture is low, seawater at the seawater side 13 enters the steam discharge pipeline 8 and meets with steam in the inclined pipe 6 with the large length-diameter ratio, introduced non-condensable gas forms an elastomer, the inclined pipe 6 with the large length-diameter ratio can further increase the speed of the seawater entering the inclined pipe 6 with the large length-diameter ratio, the seawater with a high speed enables the residual steam to rapidly collapse into small micelles, and the non-condensable gas forms elastomer micelles 15, then, when seawater collides against the elastomer micelles 15, the elastomer micelles 15 contract by the collision, and the energy generated by the collision is absorbed and buffered well, so that the water hammer is not formed in the steam discharge pipe 8, and the generation of the water hammer is further suppressed rapidly.
However, the included angle between the inclined section and the horizontal line cannot be too large, so that the seawater is prevented from entering the vertical section 5 too quickly, therefore, the included angle between the central axis of the large length-diameter ratio inclined pipe 6 and the horizontal line is not more than 5 degrees, and the length-diameter ratio of the large length-diameter ratio inclined pipe 6 is more than 40 degrees.
Further, a connecting elbow is arranged between the vertical section 5 and the inclined section, a plurality of gas pipelines 7 are arranged on the steam discharge pipeline 8, preferably, the gas pipelines 7 are arranged in parallel, and the distance between the gas pipeline 7 close to the connecting elbow and the connecting elbow is not more than 10 times of the diameter of the inclined pipeline 6 with the large length-diameter ratio. The distance between two adjacent gas pipes 7 is not more than 10 times larger than the diameter of the inclined pipe 6.
In detail, the distance from the first gas pipe 7 to the connecting bend from the vertical section 5 is not more than ten times the diameter of the large aspect ratio inclined pipe 6, and the distance between two adjacent gas pipes 7 in the plurality of gas pipes 7 is not more than ten times the diameter of the large aspect ratio inclined pipe 6. The reason is that the length of the large length-diameter ratio inclined pipe 6 is long, the water hammer is generated in the pipe randomly, and the arrangement of the plurality of gas pipes 7 can eliminate the water hammers at different positions in the large length-diameter ratio inclined pipe 6, so that the whole safety of the nuclear power device is improved.
Further, one end of the gas pipeline 7 is connected with the steam discharge pipeline 8, the other end of the gas pipeline is provided with a gas storage tank 10, and the gas storage tank 10 is provided with a gas compressor 11. The gas storage tank 10 is used for storing gas, has the function of stabilizing pressure, can avoid large gas pressure fluctuation and reduce the starting and stopping frequency of the gas compressor 11. In order to ensure that the gas entering the steam outlet line 8 is free of impurities, a gas filter can also be provided in the gas line 7.
Further, the diameter of the gas pipeline 7 is not more than 1/5 of the diameter of the large length-diameter ratio inclined pipeline 6, and the length-diameter ratio of the gas pipeline 7 is more than 20. This is because if the diameter of the gas pipe 7 is too large, the air flow rate will be too large, which is not favorable for the direct contact condensation of steam and seawater, and is not favorable for discharging the waste heat.
Further, the check valve 9 is provided adjacent to the connection of the gas pipe 7 and the steam discharge pipe 8. This is because the check valve 9 is adjacent to the connection position of the gas pipe 7 and the large length-diameter ratio inclined pipe 6, and seawater can be prevented from existing between the gas pipe 7 and the large length-diameter ratio inclined pipe 6, so that water hammer occurs in the gas pipe 7.
For the non-condensable gas, the non-condensable gas is not condensed together with steam in the process of contacting with seawater, the non-condensable gas is air, the cost can be saved, a one-way valve 9 is arranged on each gas pipeline 7, when the pressure of each gas pipeline 7 is higher than that of each inclined pipeline 6 with a large length-diameter ratio, the air enters each inclined pipeline 6 with the large length-diameter ratio and is mixed with the steam in the pipeline, when the steam is condensed to induce water hammer, the air has good compressibility as the non-condensable gas, elastomer micro-clusters 15 are formed, the water hammer pressure can be greatly reduced, and the air is discharged into the seawater under the driving of natural convection of the seawater; when the pressure of the gas pipeline 7 is smaller than the pressure of the inclined pipeline 6 with the large length-diameter ratio, the check valve is closed, seawater is prevented from flowing backwards into the cabin body, and the operation safety of the nuclear power device is ensured; once the steam condensation inducing pressure is reduced, the air automatically enters the large length-diameter ratio inclined pipe 6, the air is used as non-condensable gas for eliminating water hammer induced by steam condensation, and the process is circulated.
Although the present invention has been described with reference to a preferred embodiment, it should be understood that various changes, substitutions and alterations can be made herein without departing from the spirit and scope of the invention as defined by the appended claims.
Claims (10)
1. The nuclear power waste heat discharge device comprises a steam generation system, wherein the steam generation system comprises a liquid inlet and a steam outlet, and the steam outlet is connected with a steam discharge pipeline; the method is characterized in that:
the steam exhaust pipeline is provided with a gas pipeline for introducing non-condensable gas into the steam exhaust pipeline, and the gas pipeline is provided with a one-way valve for introducing the non-condensable gas into the steam exhaust pipeline from the gas pipeline.
2. The nuclear power waste heat removal device of claim 1, wherein:
the steam generation system also comprises a high-temperature water inlet and a cooling water outlet, and a first channel is formed between the high-temperature water inlet and the cooling water outlet; and a second channel is formed between the liquid inlet and the steam outlet, and the first channel and the second channel are isolated from each other and have heat exchange.
3. The nuclear power waste heat removal device of claim 2, wherein:
the liquid inlet is communicated with a seawater pipeline, the high-temperature water inlet is communicated with a high-temperature water outlet in the nuclear power device, and the cooling water outlet is communicated with a cooling water inlet in the nuclear power device.
4. The nuclear power waste heat removal device of any one of claims 1 to 3, wherein:
the steam discharge pipeline comprises a vertical section and an inclined section, the vertical section is connected with the steam outlet, the inclined section is an inclined pipeline with a large length-diameter ratio, an included angle between the central axis of the inclined pipeline with the large length-diameter ratio and a horizontal line is not more than 5 degrees, and the length-diameter ratio of the inclined pipeline with the large length-diameter ratio is more than 40 degrees.
5. The nuclear power waste heat removal device of claim 4, wherein:
a connecting elbow is arranged between the vertical section and the inclined section, a plurality of gas pipelines are arranged on the steam discharge pipeline, and the distance between the gas pipeline close to the connecting elbow and the connecting elbow is not more than 10 times of the diameter of the inclined pipeline with the large length-diameter ratio.
6. The nuclear power waste heat removal device of claim 5, wherein:
the distance between two adjacent gas pipelines is not more than 10 times of the diameter of the large length-diameter ratio inclined pipeline.
7. The nuclear power waste heat removal device of any one of claims 1 to 6, wherein:
one end of the gas pipeline is connected with the steam discharge pipeline, the other end of the gas pipeline is provided with a gas storage tank, and the gas storage tank is provided with a gas compressor.
8. The nuclear power waste heat removal device of any one of claims 1 to 6, wherein:
the one-way valve is disposed adjacent to a junction of the gas conduit and the vapor vent conduit.
9. The nuclear power waste heat removal device of claim 4, wherein:
the diameter of the gas pipeline is not more than 1/5 of the large length-diameter ratio of the inclined pipeline, and the ratio of the length to the diameter of the gas pipeline is more than 20.
10. The nuclear power waste heat removal device of claim 1, wherein:
the non-condensable gasses comprise air.
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|---|---|---|---|
| CN202010191183.5A CN113494704A (en) | 2020-03-18 | 2020-03-18 | Nuclear power waste heat discharging device |
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| Application Number | Priority Date | Filing Date | Title |
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| CN202010191183.5A CN113494704A (en) | 2020-03-18 | 2020-03-18 | Nuclear power waste heat discharging device |
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| CN113494704A true CN113494704A (en) | 2021-10-12 |
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Application publication date: 20211012 |